ML032370407
| ML032370407 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 08/25/2003 |
| From: | Kuo P NRC/NRR/DRIP/RLEP |
| To: | Moyer J Carolina Power & Light Co |
| Mitra, SK, NRR/DRIP/RLEP, 415-2783 | |
| Shared Package | |
| ML032370382 | List: |
| References | |
| Download: ML032370407 (24) | |
Text
Safety Evaluation Report Related to the License Renewal of the H. B. Robinson Steam Electric Plant, Unit 2 Docket No. 50-261 Carolina Power & Light Company U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation August 2003
ii ABSTRACT This safety evaluation report (SER) documents the technical review of the H.B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, known as Robinson Nuclear Plant (RNP), license renewal application (LRA) by the U.S. Nuclear Regulatory Commission (NRC) staff. By letter dated June 14, 2002, Carolina Power & Light Company (CP&L or the applicant) submitted the LRA for RNP in accordance with Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54 or the Rule). RNP is requesting renewal of the operating license for Unit 2 (License Number DPR-23) for a period of 20 years beyond the current expiration date of midnight, July 31, 2010.
RNP is adjacent to Unit 1 of the H.B. Robinson Steam Electric Plant (SEP), a coal-fired steam power plant. The plant is located on the edge of Lake Robinson, a manmade lake in Hartsville, South Carolina. The construction permit for RNP was issued by the NRC on April 13, 1967, and the operating license was issued September 23, 1970, pursuant to Section 104b of the Atomic Energy Act of 1954, as amended. The unit consists of a Westinghouse pressurized water reactor nuclear steam supply system designed to generate 2339 MW-thermal, or approximately 769 MW-electric.
This SER presents the status of the staffs review of information submitted to the NRC through August 25, 2003, the cutoff date for consideration in the SER. The staff has identified open items that must be resolved before the staff can make a determination on the application.
These items are summarized in Section 1.6 of this report. In order to close these items, the staff requires the additional information identified in the open items. The staff will present its final conclusion on the review of the RNP application in its update to this SER.
iii ABBREVIATIONS AC alternating current ACI American Concrete Institute ACRS Advisory Committee on Reactor Safeguards (NRC)
AFW auxiliary feedwater AISC American Institute of Steel Construction AISI American Iron and Steel Institute ALARA as low as reasonably achievable AMP aging management program AMR aging management review ANL Argonne National Laboratory ANSI American National Standards Institute API American Petroleum Institute ASA American Standards Association ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials ATWS anticipated transient without scram AWWA American Water Works Association B&PV boiler and pressure vessel BIT boron injection tank BMI bottom mounted instrumentation BWR boiling-water reactor CASS cast austenitic stainless steel CCMS core cooling monitor system CE Combustion Engineering, Inc.
CETS core exit thermocouple system CF chemistry factor CRD control rod drive CCW component cooling water CFR Code Of Federal Regulations CLB current licensing basis CMAA Crane Manufacturers Association of America CP&L Carolina Power & Light Co.
CRDM control rod drive mechanism CSS containment spray system CST condensate storage tank CUF cumulative usage factor CV containment vessel CVCS chemical and volume control system DBA design basis accident DBD design basis document DBE design basis earthquake dc direct current DG diesel generator DOE Department of Energy, U.S.
iv DS dedicated shutdown DSDG dedicated shutdown diesel generator EAF environmentally assisted fatigue ECCS emergency core cooling system EDB equipment database EOCI electric overhead crane institute ESS extraction steam system ET eddy current testing (NRC List of Abbreviations has this as ECT)
EDG emergency diesel generator EFPY effective full-power years EHC electrohydraulic control EJMA expansion joint manufacturers association EMA equivalent margins analysis EOF emergency operations facility EPRI Electric Power Research Institute EQ environmental qualification ER environmental report ESF engineered safety features FAC flow-accelerated corrosion Fen environmental fatigue multiplier FERC Federal Energy Regulatory Commission FMP fatigue monitoring program FP fire protection FPC Florida Power Corporation FR Federal Register FHB fuel-handling building FSAR final safety analysis report FW Feedwater GALL Generic Aging Lessons Learned (GALL) Report, NUREG-1801 GEIS generic environmental impact statement GDC general design criterion/criteria GL generic letter GSI generic safety issue HAD heat-actuated device HBRNS H.B. Robinson Nuclear Station HEPA high-efficiency particulate air HELB high energy line break HPSI high pressure safety injection HVAC heating, ventilation, and air conditioning I&C Instrumentation and control IA instrument air IASCC irradiation assisted stress corrosion cracking IEEE Institute of Electrical and Electronic Engineers IGA intergranular attack IGSCC intergranular stress-corrosion cracking IR insulation resistance ISG interim staff guidance ILRT integrated leak rate test (Containment Type A Test)
IN Information Notice
v INPO Institute Of Nuclear Power Operations IPA integrated plant assessment ISI inservice inspection IVSW isolation valve seal water LBB Leak before break LOCA loss-of-coolant accident LR license renewal LRA license renewal application MRP Material Reliability Project (EPRI)
MSS main steam system MCC Motor control center MDAFW motor-driven auxiliary feedwater MIC microbiologically induced corrosion MOV motor-operated valve MSIV main steam isolation valve NACE National Association of Corrosion Engineers NDE nondestructive examination NEPA National Environmental Policy Act of 1969 NPAR nuclear plant aging research NPS nominal pipe size NUREG NRC technical report designation (Nuclear Regulatory Commission)
NEI Nuclear Energy Institute NEMA National Electrical Manufacturers Association NFPA National Fire Protection Association NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System OE operating experience OCB oil circuit breaker P&I piping and instrumentation PMAMP preventive maintenance aging management program PAP personnel access portal pH concentration of hydrogen ions PM preventive maintenance PORV power-operated relief valve PPS penetration pressurization system PRT pressurizer relief tank P-T pressure-temperature PTS pressurized thermal shock PVC polyvinyl Chloride PWR pressurized water reactor PWSCC primary water stress corrosion cracking PWST primary water storage tank PZR pressurizer QA quality assurance QC quality control RAB reactor auxiliary building RAI request for additional information RCDT reactor coolant drain tank RCP reactor coolant pump
vi RCPB reactor coolant pressure boundary RCS reactor coolant system REDS radioactive equipment drain system RG regulatory guide RHR residual heat removal RMS radiation monitoring system RNP Robinson Nuclear Plant RO/RFO refueling outage RPS reactor protection system RPV reactor pressure vessel RTPTS reference temperature, pressurized thermal shock RTS reactor trip system RV reactor vessel RWST refueling water storage tank RTD resistance temperature detector RVLIS reactor vessel level instrumentation system scss steam cycle sampling system SEP steam electric plant SGB steam generator blowdown SGBS steam generator blowdown system SGTR steam generator tube rupture SOC Statement of Consideration SRP-LR Standard Review Plan for License Renewal SUT startup transformer SAR safety analysis report SBO station blackout SCs structures and components SCC stress corrosion cracking SDAFW steam-driven auxiliary feedwater SER safety evaluation report SFP spent fuel pit SG steam Generator SI safety injection SIT structural integrity test SR silicone rubber SRP standard review plan SSCs systems, structures, and components SFPCS spent fuel pit cooling system SWS service water system TDR time domain reflectometry TGSCC transgranular stress corrosion cracking TID total integrated dose TLAA time-limited aging analysis TSC Technical Support Center UAT unit auxiliary transformer UV ultraviolet UFSAR Updated Final Safety Analysis Report USAS United States Of America Standards USE Upper Shelf Energy
vii UT ultrasonic test Vac volts alternating current Vdc volts direct current VHP vessel head penetration VCT volume control tank WCAP Westinghouse Commercial Atomic Power WDS waste disposal system WOG Westinghouse Owners Group
viii TABLE OF CONTENTS ABSTRACT
............................................................... ii ABBREVIATIONS.......................................................... iii 1 INTRODUCTION AND GENERAL DISCUSSION............................... 1-1 1.1 Introduction..................................................... 1-1 1.2 License Renewal Background...................................... 1-2 1.2.1 Safety Review........................................... 1-3 1.2.2 Environmental Review..................................... 1-4 1.3 Summary of Principal Review Matters................................ 1-5 1.3.1 Westinghouse Topical Reports.............................. 1-6 1.4 Interim Staff Guidance............................................ 1-7 1.5 Summary of Open Items........................................... 1-9 1.6 Summary of Confirmatory Items.................................... 1-10 1.7 Summary of Proposed License Conditions............................ 1-20 2.0 STRUCTURES AND COMPONENTS SUBJECT TO AN AGING MANAGEMENT REVIEW.......................................... 2-1 2.1 Scoping and Screening Methodology................................ 2-2 2.1.1 Introduction............................................. 2-2 2.1.2 Summary of Technical Information in the Application.............. 2-2 2.1.2.1 Scoping Methodology............................... 2-3 2.1.2.1.1 Application of the Scoping Criteria in 10 CFR 54.4(a)........................... 2-3 2.1.2.1.2 Documentation Sources Used for Scoping and Screening............................. 2-5 2.1.2.2 Screening Methodology............................. 2-6 2.1.2.2.1 Mechanical Screening....................... 2-6 2.1.2.2.2 Structural Screening
........................ 2-7 2.1.2.2.3 Electrical and Instrumentation and Controls (I & C) Screening................ 2-7 2.1.3 Staff Evaluation......................................... 2-8 2.1.3.1 Scoping Methodology.............................. 2-9 2.1.3.1.1 Application of the Scoping Criteria in 10 CFR 54.4(a).......................... 2-9 2.1.3.1.2 Mechanical Scoping........................ 2-13 2.1.3.1.3 Structural Scoping......................... 2-14 2.1.3.1.4 Electrical and Instrumentation and Controls Scoping...................... 2-15 2.1.3.2 Screening Methodology....................... 2-15 2.1.3.2.1 Mechanical Screening.................. 2-15 2.1.3.2.2 Structural Screening................... 2-16 2.1.3.2.3 Electrical and Instrumentation and Controls Screening................. 2-16 2.1.4 Evaluation Findings..................................... 2-17
ix 2.2 Plant-Level Scoping Results....................................... 2-18 2.2.1 Summary of Technical Information in the Application............. 2-18 2.2.2 Staff Evaluation.......................................... 2-18 2.2.3 Evaluation Findings....................................... 2-20 2.3 Scoping and Screening Results: Mechanical Systems................... 2-20 2.3.1 Reactor Systems........................................ 2-21 2.3.1.1 Reactor Coolant System Piping...................... 2-21 2.3.1.1.1 Summary of Technical Information in the Application.......................... 2-21 2.3.1.1.2 Staff Evaluation........................... 2-23 2.3.1.1.3 Conclusions.............................. 2-23 2.3.1.2 Reactor Coolant Pumps............................ 2-24 2.3.1.2.1 Summary of Technical Information in the Application.......................... 2-24 2.3.1.2.2 Staff Evaluation........................... 2-25 2.3.1.2.3 Conclusions.............................. 2-25 2.3.1.3 Pressurizer..................................... 2-25 2.3.1.3.1 Summary of Technical Information in the Application.......................... 2-25 2.3.1.3.2 Staff Evaluation........................... 2-26 2.3.1.3.3 Conclusions.............................. 2-28 2.3.1.4 Reactor Pressure Vessel........................... 2-28 2.3.1.4.1 Summary of Technical Information in the Application.......................... 2-28 2.3.1.4.2 Staff Evaluation........................... 2-29 2.3.1.4.3 Conclusions.............................. 2-29 2.3.1.5 Reactor Vessel Internals........................... 2-29 2.3.1.5.1 Summary of Technical Information in the Application.......................... 2-29 2.3.1.5.2 Staff Evaluation........................... 2-30 2.3.1.5.3 Conclusions.............................. 2-31 2.3.1.6 Steam Generators................................ 2-31 2.3.1.6.1 Summary of Technical Information in the Application.......................... 2-31 2.3.1.6.2 Staff Evaluation........................... 2-32 2.3.1.6.3 Conclusions.............................. 2-34 2.3.1.7 Reactor Vessel Level Instrumentation................ 2-34 2.3.1.7.1 Summary of Technical Information in the Application.......................... 2-34 2.3.1.7.2 Staff Evaluation........................... 2-34 2.3.1.7.3 Conclusions.............................. 2-35 2.3.1.8 Evaluation Findings............................... 2-35 2.3.2 Engineered Safety Features Systems........................ 2-35 2.3.2.1 Residual Heat Removal System..................... 2-35 2.3.2.1.1 Summary of Technical Information in the Application.......................... 2-35 2.3.2.1.2 Staff Evaluation........................... 2-36 2.3.2.1.3 Conclusions.............................. 2-36 2.3.2.2 Safety Injection System............................ 2-36
x 2.3.2.2.1 Summary of Technical Information in the Application.......................... 2-36 2.3.2.2.2 Staff Evaluation........................... 2-37 2.3.2.2.3 Conclusions.............................. 2-37 2.3.2.3 Containment Spray System......................... 2-37 2.3.2.3.1 Summary of Technical Information in the Application.......................... 2-37 2.3.2.3.2 Staff Evaluation........................... 2-38 2.3.2.3.3 Conclusions.............................. 2-40 2.3.2.4 Containment Air Recirculation Cooling System.......... 2-40 2.3.2.4.1 Summary of Technical Information in the Application.......................... 2-40 2.3.2.4.2 Staff Evaluation........................... 2-41 2.3.2.4.3 Conclusions.............................. 2-43 2.3.2.5 Containment Isolation System....................... 2-43 2.3.2.5.1 Summary of Technical Information in the Application.......................... 2-43 2.3.2.5.2 Staff Evaluation........................... 2-44 2.3.2.5.3 Conclusions.............................. 2-46 2.3.3 Auxiliary Systems........................................ 2-46 2.3.3.1 Sampling Systems................................ 2-46 2.3.3.1.1 Summary of Technical Information in the Application.......................... 2-46 2.3.3.1.2 Staff Evaluation........................... 2-47 2.3.3.1.3 Conclusions
............................. 2-48 2.3.3.2 Service Water System............................. 2-49 2.3.3.2.1 Summary of Technical Information in the Application.......................... 2-49 2.3.3.2.2 Staff Evaluation........................... 2-49 2.3.3.2.3 Conclusions.............................. 2-50 2.3.3.3 Component Cooling Water System................... 2-51 2.3.3.3.1 Summary of Technical Information in the Application.......................... 2-51 2.3.3.3.2 Staff Evaluation........................... 2-51 2.3.3.3.3 Conclusions.............................. 2-52 2.3.3.4 Chemical and Volume Control System
................ 2-52 2.3.3.4.1 Summary of Technical Information in the Application.......................... 2-52 2.3.3.4.2 Staff Evaluation........................... 2-53 2.3.3.4.3 Conclusions.............................. 2-53 2.3.3.5 Instrument Air System............................. 2-53 2.3.3.5.1Summary of Technical Information in the Application........................... 2-53 2.3.3.5.2 Staff Evaluation........................... 2-54 2.3.3.5.3 Conclusions.............................. 2-54 2.3.3.6 Nitrogen Supply/Blanketing System................... 2-54 2.3.3.6.1 Summary of Technical Information in the Application.......................... 2-54 2.3.3.6.2 Staff Evaluation........................... 2-54
2.3.3.6.3 Conclusions.............................. 2-55 2.3.3.7 Radioactive Equipment Drain....................... 2-55 2.3.3.7.1 Summary of Technical Information in the Application.......................... 2-55 2.3.3.7.2 Staff Evaluation........................... 2-56 2.3.3.7.3 Conclusions.............................. 2-57 2.3.3.8 Primary and Demineralized Water System............. 2-57 2.3.3.8.1 Summary of Technical Information in the Application.......................... 2-57 2.3.3.8.2 Staff Evaluation........................... 2-57 2.3.3.8.3 Conclusions
............................. 2-59 2.3.3.10 Containment Purge System........................ 2-62 2.3.3.10.1 Summary of Technical Information in the Application......................... 2-62 2.3.3.10.2 Staff Evaluation.......................... 2-63 2.3.3.10.3 Conclusions............................. 2-64 2.3.3.11 Rod Drive Cooling System......................... 2-64 2.3.3.11.1 Summary of Technical Information in the Application......................... 2-64 2.3.3.11.2 Staff Evaluation.......................... 2-65 2.3.3.11.3 Conclusions............................. 2-67 2.3.3.12 Heating Ventilation and Air Conditioning-Auxiliary Building..................... 2-68 2.3.3.12.1 Summary of Technical Information in the Application......................... 2-68 2.3.3.12.2 Staff Evaluation.......................... 2-69 2.3.3.12.3 Conclusions............................. 2-71 2.3.3.13 Heating, Ventilation, and Air Conditioning-Control Room Area.................... 2-72 2.3.3.13.1 Summary of Technical Information in the Application......................... 2-72 2.3.3.13.2 Staff Evaluation.......................... 2-73 2.3.3.13.3 Conclusions............................. 2-76 2.3.3.14 Heating, Ventilation, and Air Conditioning-Fuel Handling Building
................. 2-76 2.3.3.14.1 Summary of Technical Information in the Application......................... 2-76 2.3.3.14.2 Staff Evaluation.......................... 2-77 2.3.3.14.3 Conclusions............................. 2-79 2.3.3.15 Fire Protection System........................... 2-80 2.3.3.15.1 Summary of Technical Information in the Application......................... 2-80 2.3.3.15.2 Staff Evaluation.......................... 2-81 2.3.3.15.3 Conclusions............................. 2-86 2.3.3.16 Diesel Generator System.......................... 2-86 2.3.3.16.1 Summary of Technical Information in the Application......................... 2-86 2.3.3.15.2 Staff Evaluation.......................... 2-87 2.3.3.15.3 Conclusions............................. 2-87 2.3.3.17 Dedicated Shutdown Diesel Generator............... 2-87
xii 2.3.3.17.1 Summary of Technical Information in the Application......................... 2-88 2.3.3.17.2 Staff Evaluation.......................... 2-88 2.3.3.17.3 Conclusions............................. 2-88 2.3.3.18 Emergency Operations Facility/Technical Support Center (EOF/TSC) Security Diesel Generator... 2-88 2.3.3.18.1 Summary of Technical Information in the Application......................... 2-88 2.3.3.18.2 Staff Evaluation.......................... 2-89 2.3.3.18.3 Conclusions............................. 2-89 2.3.3.19 Fuel Oil System................................. 2-89 2.3.3.18.1 Summary of Technical Information in the Application......................... 2-89 2.3.3.18.2 Staff Evaluation.......................... 2-90 2.3.3.18.3 Conclusions............................. 2-90 2.3.4 Steam and Power Conversion Systems....................... 2-90 2.3.4.1 Turbine System.................................. 2-90 2.3.4.1.1 Summary of Technical Information in the Application.......................... 2-90 2.3.4.1.2 Staff Evaluation........................... 2-90 2.3.4.1.3 Conclusions.............................. 2-91 2.3.4.2 Electro-Hydraulic Control System.................... 2-91 2.3.4.2.1 Summary of Technical Information in the Application.......................... 2-91 2.3.4.2.2 Staff Evaluation........................... 2-92 2.3.4.2.3 Conclusions.............................. 2-92 2.3.4.3 Turbine Generator Lube Oil System.................. 2-92 2.3.4.3.1 Summary of Technical Information in the Application.......................... 2-92 2.3.4.3.2 Staff Evaluation........................... 2-93 2.3.4.3.3 Conclusions.............................. 2-93 2.3.4.4 Extraction Steam System
.......................... 2-93 2.3.4.4.1 Summary of Technical Information in the Application.......................... 2-93 2.3.4.4.2 Staff Evaluation........................... 2-94 2.3.4.4.3 Conclusions.............................. 2-95 2.3.4.5 Main Steam System
.............................. 2-95 2.3.4.5.1 Summary of Technical Information in the Application.......................... 2-95 2.3.4.5.2 Staff Evaluation........................... 2-96 2.3.4.5.3 Conclusions.............................. 2-96 2.3.4.6 Steam Generator Blowdown System.................. 2-96 2.3.4.6.1 Summary of Technical Information in the Application.......................... 2-96 2.3.4.6.2 Staff Evaluation........................... 2-97 2.3.4.6.3 Conclusions
............................. 2-97 2.3.4.7 Steam Cycle Sampling............................ 2-97 2.3.4.7.1 Summary of Technical Information
xiii in the Application................................. 2-97 2.3.4.7.2 Staff Evaluation........................... 2-97 2.3.4.7.3 Conclusions.............................. 2-98 2.3.4.8 Feedwater System................................ 2-99 2.3.4.8.1 Summary of Technical Information in the Application.......................... 2-99 2.3.4.8.2 Staff Evaluation........................... 2-99 2.3.4.8.3 Conclusions.............................. 2-99 2.3.4.9 Auxiliary Feedwater System
........................ 2-99 2.3.4.9.1 Summary of Technical Information in the Application.......................... 2-99 2.3.4.9.2 Staff Evaluation.......................... 2-100 2.3.4.9.3 Conclusions............................. 2-101 2.3.4.10 Condensate System............................ 2-102 2.3.4.10.1 Summary of Technical Information in the Application........................ 2-102 2.3.4.10.2 Staff Evaluation......................... 2-102 2.3.4.10.3 Conclusions............................ 2-103 2.3.4.11 Steam Generator Chemical Addition................ 2-104 2.3.4.11.1 Summary of Technical Information in the Application.............................. 2-104 2.3.4.11.2 Staff Evaluation......................... 2-104 2.3.4.11.3 Conclusions............................ 2-104 2.3.4.12 Circulating Water System........................ 2-105 2.3.4.12.1 Summary of Technical Information in the Application........................ 2-105 2.3.4.12.2 Staff Evaluation......................... 2-105 2.3.4.12.3 Conclusions
........................... 2-105 2.4 Scoping and Screening Results: Structures........................ 2-106 2.4.1 Containment........................................... 2-106 2.4.1.1 Containment Structure............................ 2-106 2.4.1.2 Containment Internal Structural Components.......... 2-107 2.4.1.3 Containment External Structural Components.......... 2-109 2.4.1.4 Summary of Technical Information in the Application.... 2-109 2.4.1.5 Staff Evaluation................................. 2-110 2.4.1.6 Conclusions.................................... 2-111 2.4.2 Other Structures........................................ 2-111 2.4.2.1 Reactor Auxiliary Building.......................... 2-112 2.4.2.1.1 Summary of Technical Information in the Application......................... 2-112 2.4.2.1.2 Staff Evaluation.......................... 2-113 2.4.2.1.3 Conclusions
............................ 2-114 2.4.2.2 Fuel Handling Building............................ 2-114 2.4.2.2.1 Summary of Technical Information in the Application......................... 2-114 2.4.2.2.2 Staff Evaluation.......................... 2-115 2.4.2.2.3 Conclusions
............................ 2-116 2.4.2.3 Turbine Building................................. 2-116 2.4.2.3.1 Summary of Technical Information
xiv in the Application......................... 2-116 2.4.2.3.2 Staff Evaluation.......................... 2-117 2.4.2.3.3 Conclusions............................. 2-118 2.4.2.4 Dedicated Shutdown Diesel Generator Building........ 2-118 2.4.2.4.1 Summary of Technical Information in the Application......................... 2-118 2.4.2.4.2 Staff Evaluation.......................... 2-118 2.4.2.4.3 Conclusions............................. 2-119 2.4.2.5 Radwaste Building............................... 2-119 2.4.2.5.1 Summary of Technical Information in the Application......................... 2-119 2.4.2.5.2 Staff Evaluation.......................... 2-120 2.4.2.5.3 Conclusions............................. 2-120 2.4.2.6 Intake Structures................................ 2-121 2.4.2.6.1 Summary of Technical Information in the Application......................... 2-121 2.4.2.6.2 Staff Evaluation.......................... 2-121 2.4.2.6.3 Conclusions............................. 2-122 2.4.2.7 North Service Water Header Enclosure............... 2-123 2.4.2.7.1 Summary of Technical Information in the Application......................... 2-123 2.4.2.7.2 Staff Evaluation.......................... 2-123 2.4.2.7.3 Conclusions............................. 2-124 2.4.2.8 Emergency Operations Facility/Technical Support Center Security Diesel Generator Building................... 2-124 2.4.2.8.1Summary of Technical Information in the Application......................... 2-124 2.4.2.8.2 Staff Evaluation.......................... 2-125 2.4.2.8.3 Conclusions............................. 2-125 2.4.2.9 Discharge Structures............................. 2-125 2.4.2.9.1Summary of Technical Information in the Application......................... 2-126 2.4.2.9.2 Staff Evaluation.......................... 2-126 2.4.2.9.3 Conclusions............................. 2-126 2.4.2.10 Lake Robinson Dam............................ 2-127 2.4.2.10.1 Summary of Technical Information in the Application........................ 2-127 2.4.2.10.2 Staff Evaluation......................... 2-127 2.4.2.10.3 Conclusions............................ 2-128 2.4.2.11 Pipe Restraint Tower............................ 2-128 2.4.2.11.1 Summary of Technical Information in the Application........................ 2-128 2.4.2.11.2 Staff Evaluation......................... 2-129 2.4.2.11.3 Conclusions............................ 2-129 2.4.2.12 Yard Structures and Foundations.................. 2-129 2.4.2.12.1 Summary of Technical Information in the Application........................ 2-129 2.4.2.12.2 Staff Evaluation......................... 2-130 2.4.2.12.3 Conclusions............................ 2-132
xv 2.4.2.13 Refueling System
.............................. 2-132 2.4.2.13.1 Summary of Technical Information in the Application........................ 2-132 2.4.2.13.2 Staff Evaluation......................... 2-132 2.4.2.13.3 Conclusions............................ 2-133 2.4.3 Evaluation Findings..................................... 2-134 2.5 Scoping and Screening Results: Electrical/Instrumentation and Control Systems......................................... 2-134 2.5.1 Bus Duct............................................. 2-135 2.5.1.1 Summary of Technical Information in the Application.... 2-135 2.5.1.2 Staff Evaluation................................. 2-135 2.5.1.3 Conclusions.................................... 2-136 2.5.2 Insulated Cables and Connections.......................... 2-136 2.5.2.1 Summary of Technical Information in the Application.... 2-136 2.5.2.2 Staff Evaluation................................. 2-136 2.5.2.3 Conclusion..................................... 2-137 2.5.3 Electrical/Instrumentation and Control Penetration Assemblies.... 2-137 2.5.3.1 Summary of Technical Information in the Application.... 2-138 2.5.3.2 Staff Evaluation................................. 2-138 2.5.3.3 Conclusions.................................... 2-138 2.5.4 Station Blackouts....................................... 2-139 2.5.4.1 Summary of Technical Information in the Application.... 2-139 2.5.4.2 Staff Evaluation................................. 2-140 2.5.4.3 Conclusion..................................... 2-141 2.5.5 Evaluation Findings..................................... 2-141 3.0 AGING MANAGEMENT REVIEW....................................... 3-1 3.0.1 The GALL Format for the License Renewal Application............ 3-2 3.0.2 The Staffs Review Process for GALL......................... 3-3 3.0.3 Aging Management Programs............................... 3-4 3.0.3.1 Metal Fatigue of Reactor Coolant Pressure Boundary (Fatigue Monitoring Program)...................................... 3-8 3.0.3.1.1 Summary of Technical Information in the Application 3-8 3.0.3.1.2 Staff Evaluation............................ 3-9 3.0.3.1.3 Conclusions
............................. 3-11 3.0.3.2 ASME Section XI, Inservice Inspection, Subsections IWB, IWC, and IWD Program
...................................... 3-11 3.0.3.2.1 Summary of Technical Information in the Application...................................... 3-11 3.0.3.2.2 Staff Evaluation.......................... 3-12 3.0.3.2.3 Conclusions
............................. 3-12 3.0.3.3 Water Chemistry Program.......................... 3-13 3.0.3.3.1 Summary of Technical Information in the Application...................................... 3-13 3.0.3.3.2 Staff Evaluation........................... 3-13 3.0.3.3.3 UFSAR Supplement....................... 3-16 3.0.3.3.4 Conclusions
............................. 3-16 3.0.3.4 Boric Acid Corrosion Program....................... 3-16 3.0.3.4.1 Summary of Technical Information in the
xvi Application...................................... 3-16 3.0.3.4.2 Staff Evaluation........................... 3-17 3.0.3.4.3 UFSAR Supplement....................... 3-21 3.0.3.4.4 Conclusions
............................. 3-22 3.0.3.5 Flow Accelerated Corrosion Program................. 3-22 3.0.3.5.1 Summary of Technical Information in the Application...................................... 3-22 3.0.3.5.2 Staff Evaluation........................... 3-23 3.0.3.5.3 UFSAR Supplement....................... 3-27 3.0.3.5.4 Conclusions
............................. 3-27 3.0.3.6 Bolting Integrity Program........................... 3-28 3.0.3.6.1 Summary of Technical Information in the Application...................................... 3-28 3.0.3.6.2 Staff Evaluation........................... 3-29 3.0.3.6.3 Conclusions
............................. 3-30 3.0.3.7 Open-Cycle Cooling Water System Program........... 3-30 3.0.3.7.1 Summary of Technical Information in the Application...................................... 3-30 3.0.3.7.2 Staff Evaluation........................... 3-31 3.0.3.7.3 Conclusions
............................. 3-32 3.0.3.8 Closed-Cycle Cooling Water System Program.......... 3-32 3.0.3.8.1 Summary of Technical Information in the Application...................................... 3-32 3.0.3.8.2 Staff Evaluation........................... 3-33 3.0.3.8.3 Conclusions
............................. 3-33 3.0.3.9 One-Time Inspection Program....................... 3-34 3.0.3.9.1 Summary of Technical Information in the Application...................................... 3-34 3.0.3.9.2 Staff Evaluation........................... 3-34 3.0.3.9.3 Conclusions
............................. 3-35 3.0.3.10 Selective Leaching of Materials Program.............. 3-35 3.0.3.10.1 Summary of Technical Information in the Application...................................... 3-35 3.0.3.10.2 Staff Evaluation.......................... 3-36 3.0.3.10.3 Conclusions
............................ 3-36 3.0.3.11 Systems Monitoring Program
...................... 3-37 3.0.3.11.1 Summary of Technical Information in the Application...................................... 3-37 3.0.3.11.2 Staff Evaluation.......................... 3-37 3.0.3.11.3 Conclusions
............................ 3-39 3.0.3.12 Preventive Maintenance Program................... 3-39 3.0.3.12.1 Summary of Technical Information in the Application...................................... 3-39 3.0.3.12.2 Staff Evaluation.......................... 3-40 3.0.3.12.3 Conclusions
............................ 3-42 3.0.4 RNP Quality Assurance Program Attributes Integral to Aging Management Programs................................................... 3-43 3.0.4.1 Summary of Technical Information in Application......... 3-43 3.0.4.2 Staff Evaluation.................................. 3-44
xvii 3.0.4.3 Conclusions..................................... 3-44 3.1 Reactor Systems............................................... 3-45 3.1.1 Summary of Technical Information in the Application............ 3-45 3.1.2 Staff Evaluation........................................ 3-46 3.1.2.1 Aging Management Evaluations in the GALL Report That Are Relied On for License Renewal, and Which Do not Require Further Evaluation.................... 3-51 3.1.2.2 Aging Management Evaluations in the GALL Report That Are Relied On for License Renewal, For Which GALL Recommends Further Evaluation............... 3-71 3.1.2.2.1 Cumulative Fatigue Damage............. 3-71 3.1.2.2.2 Loss of Material Due to Pitting and Crevice Corrosion............................ 3-73 3.1.2.2.3 Loss of Fracture Toughness Due to Neutron Irradiation Embrittlement and Dimension Changes Due to Void Swelling................... 3-74 3.1.2.2.4 Crack Initiation and Growth Due to Thermal and Mechanical Loading or Stress-Corrosion Cracking............................ 3-77 3.1.2.2.5 Crack Growth Due to Cyclic Loading....... 3-80 3.1.2.2.6 Changes in Dimension Due to Void Swelling
................................... 3-81 3.1.2.2.7 Crack Initiation and Growth Due to Stress-Corrosion Cracking or Primary Water Stress-Corrosion Cracking.................... 3-83 3.1.2.2.8 Crack Initiation and Growth Due to Stress-Corrosion Cracking or Irradiation-Assisted Stress Corrosion Cracking.................... 3-88 3.1.2.2.9 Loss of Preload Due to Stress Relaxation
................................... 3-89 3.1.2.2.10 Loss of Section Thickness Due to Erosion
................................... 3-89 3.1.2.2.11 Crack Initiation and Growth due to Primary Water Stress-Corrosion Cracking, Outer-Diameter Stress-Corrosion Cracking, or Intergranular Attack, Loss of Material Due to Wastage and Pitting Corrosion, Loss of Section Thickness Due to Fretting and Wear, or Denting Due to Corrosion of Carbon Steel Tube Support Plate......... 3-91 3.1.2.2.12 Loss of Section Thickness (Loss of Material) Due to Flow-Accelerated Corrosion............ 3-94 3.1.2.2.13 Ligament Cracking due to Corrosion.......... 3-96 3.1.2.2.14 Loss of Material Due to Flow-Accelerated Corrosion....................................... 3-97 3.1.2.2.15 Conclusions.......................... 3-98 3.1.2.3 Aging Management Programs (System-Specific)........ 3-98 3.1.2.3.1 Reactor Head Closure Studs Program......... 3-99 3.1.2.3.2 Nickel-Alloy Nozzles and Penetrations Program
...................................... 3-101
xviii 3.1.2.3.3 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Program..................... 3-105 3.1.2.3.4 PWR Vessel Internals Program............. 3-109 3.1.2.3.5 Steam Generator Tube Integrity Program...... 3-114 3.1.2.3.6 Reactor Vessel Surveillance Program......... 3-120 3.1.2.3.7 Flux Thimble Eddy Current Inspection Program. 3-126 3.1.2.4 Aging Management of Plant-Specific Components...... 3-131 3.1.2.4.1 Reactor Coolant System Piping
............. 3-131 3.1.2.4.2 Reactor Coolant Pumps................... 3-140 3.1.2.4.3 Pressurizer............................. 3-140 3.1.2.4.4 Reactor Vessel.......................... 3-143 3.1.2.4.5 Reactor Vessel Internals.................. 3-148 3.1.2.4.6 Steam Generator
........................ 3-156 3.1.2.4.7 Reactor Vessel Level Instrumentation........ 3-167 3.1.3 Evaluation Findings..................................... 3-168 3.2 Engineered Safety Features Systems
.............................. 3-169 3.2.1 Summary of Technical Information in the Application............ 3-169 3.2.2 Staff Evaluation........................................ 3-169 3.2.2.1 Aging Management Evaluations in the GALL Report that Are Relied on for License Renewal, Which Do Not Require Further Evaluation.. 3-172 3.2.2.2 Aging Management Evaluations in the GALL Report that Are Relied on for License Renewal, For Which GALL Recommends Further Evaluation.......................... 3-173 3.2.2.2.1 Cumulative Fatigue Damage................ 3-173 3.2.2.2.2 Loss of Material Due to General Corrosion.... 3-173 3.2.2.2.3 Local Loss of Material Due to Pitting and Crevice Corrosion................................. 3-174 3.2.2.2.4 Local Loss of Material Due to Microbiologically Influenced Corrosion........................ 3-175 3.2.2.2.5 Local Loss of Material Due to Erosion......... 3-176 3.2.2.2.6 Loss of Material Due to General Corrosion..... 3-176 3.2.2.2.7 Conclusions
............................ 3-177 3.2.2.3 Aging Management Program for ESF System Components 3-177 3.2.2.4 Aging Management Review of Plant-Specific ESF System Components.................................... 3-177 3.2.2.4.1 Residual Heat Removal System............. 3-177 3.2.2.4.2 Safety Injection System.................... 3-180 3.2.2.4.3 Containment Spray System................. 3-183 3.2.2.4.4 Containment Air Recirculation Cooling System.. 3-186 3.2.2.4.5 Containment Isolation System............... 3-188 3.2.3 Evaluation Findings..................................... 3-191 3.3 Auxiliary Systems............................................. 3-192 3.3.1 Summary of Technical Information in the Application............ 3-192 3.3.2 Staff Evaluation........................................ 3-193 3.3.2.1 Aging Management Evaluations in the GALL Report that Are Relied on for License Renewal, Which Do Not Require Further Evaluation......................... 3-198
xix 3.3.2.2 Aging Management Evaluations in the GALL Report that Are Relied on for License Renewal, For Which GALL Recommends Further Evaluation.............. 3-198 3.3.2.2.1 Loss of Material due to General, Pitting, and Crevice Corrosion................................ 3-198 3.3.2.2.2 Hardening and Cracking or Loss of Strength Due to Elastomer Degradation or Loss of Material due to Wear.............................. 3-199 3.3.2.2.3 Cumulative Fatigue Damage................ 3-200 3.3.2.2.4 Crack Initiation and Growth Due to Cracking or Stress Corrosion Cracking......................... 3-200 3.3.2.2.5 Loss of Material Due to General, Microbiologically-Influenced, Pitting, and Crevice Corrosion.. 3-201 3.3.2.2.6 Loss of Material Due to General, Galvanic, Pitting, and Crevice Corrosion.......................... 3-202 3.3.2.2.7 Loss of Material Due to General, Pitting, Crevice, and Microbiologically Influenced Corrosion, and Biofouling........................... 3-202 3.3.2.2.8 Crack Initiation and Growth Due to Stress Corrosion Cracking and Cyclic Loading.................. 3-203 3.3.2.2.9 Reduction of Neutron-Absorbing Capacity and Loss of Material Due to General Corrosion
..... 3-204 3.3.2.2.10 Loss of Material Due to General, Pitting, Crevice, and Microbiologically Influenced Corrosion. 3-204 3.3.2.2.11 Conclusions
........................... 3-205 3.3.2.3 Aging Management Programs (System-Specific)....... 3-205 3.3.2.3.1 Inspection of Overhead Heavy Load and Light Load Handling Systems Program................... 3-206 3.3.2.3.2 Fire Protection Program................... 3-209 3.3.2.3.3 Fire Water System Program................ 3-211 3.3.2.3.4 Buried Piping and Tanks Surveillance Program. 3-213 3.3.2.3.5 Above Ground Carbon Steel Tanks Program... 3-221 3.3.2.3.6 Fuel Oil Chemistry Program................ 3-226 3.3.2.3.7 Buried Piping and Tanks Inspection Program... 3-235 3.3.2.4 Aging Management of Plant-Specific Components...... 3-242 3.3.2.4.1 Sampling Systems....................... 3-242 3.3.2.4.2 Service Water System
.................... 3-244 3.3.2.4.3 Component Cooling Water System........... 3-247 3.3.2.4.4 Chemical and Volume Control System........ 3-249 3.3.2.4.5 Instrument Air System..................... 3-252 3.3.2.4.6 Nitrogen Supply/Blanketing System.......... 3-256 3.3.2.4.7 Radioactive Equipment Drains.............. 3-258 3.3.2.4.8 Primary and Demineralized Water System..... 3-260 3.3.2.4.9 Spent Fuel Pool Cooling System............. 3-263 3.3.2.4.10 Containment Purge System............... 3-265 3.3.2.4.11 Rod Drive Cooling System................ 3-267 3.3.2.4.12 Heating Ventilation, and Air Conditioning Auxiliary Building.................................. 3-269
xx 3.3.2.4.13 Heating Ventilation and Air Conditioning Control Room Area
.................................... 3-272 3.3.2.4.14 Heating Ventilation and Air Conditioning Fuel Handling Building.................................. 3-274 3.3.2.4.15 Fire Protection System................... 3-276 3.3.2.4.16 Diesel Generator System................. 3-278 3.3.2.4.17 Dedicated Shutdown Diesel Generator....... 3-281 3.3.2.4.18 EOF/TSC Security Diesel Generator......... 3-284 3.3.2.4.19 Fuel Oil System......................... 3-287 3.3.2.5 General AMR Issues............................. 3-290 3.3.2.5.1 Wear Degradation of Elastomer Components... 3-290 3.3.2.5.2 Closure Bolting.......................... 3-291 3.3.2.5.3 External Environments.................... 3-292 3.3.2.5.4 Boric Acid Corrosion for Galvanized Steel Component..................................... 3-293 3.3.2.5.5 Monitoring of Leakage Detection............. 3-293 3.3.3 Evaluation Findings..................................... 3-294 3.4 Steam and Power Conversion Systems............................. 3-295 3.4.1 Summary of Technical Information in the Application............ 3-295 3.4.2 Staff Evaluation........................................ 3-295 3.4.2.1 Aging Management Evaluations in the GALL Report that Are Relied on for License Renewal, Which Do Not Require Further Evaluation...................................... 3-298 3.4.2.2 Aging Management Evaluations in the GALL Report that Are Relied on for License Renewal, For Which GALL Recommends Further Evaluation............................... 3-298 3.4.2.2.1 Cumulative Fatigue Damage................ 3-298 3.4.2.2.2 Loss of Material Due to General, Pitting, and Crevice Corrosion................................. 3-299 3.4.2.2.3 Loss of Material Due to General, Pitting, and Crevice Corrosion, Microbiologically Influenced Corrosion, and Biofouling................................ 3-300 3.4.2.2.4 Loss of Material Due to General Corrosion..... 3-301 3.4.2.2.5 Loss of Material Due to General, Pitting, Crevice, and Microbiologically Influenced Corrosion
.......... 3-301 3.4.2.2.6 Conclusions
............................ 3-303 3.4.2.3 Aging Management Programs for Steam and Power Conversion Systems....................................... 3-304 3.4.2.3.1 There are no plant-specific AMPs for the steam and power conversion systems.................... 3-304 3.4.2.4 Aging Management of Plant-Specific Components...... 3-304 3.4.2.4.1 Turbine System.......................... 3-304 3.4.2.4.2 Electro-Hydraulic Control System............ 3-305 3.4.2.4.3 Turbine Generator Lube Oil System.......... 3-305 3.4.2.4.4 Extraction Steam System.................. 3-305 3.4.2.4.5 Main Steam............................. 3-306 3.4.2.4.6 Steam Generator Blowdown System.......... 3-309 3.4.2.4.7 Steam Cycle Sampling.................... 3-312 3.4.2.4.8 Feedwater System....................... 3-314
xxi 3.4.2.4.9 Auxiliary Feedwater System................ 3-317 3.4.2.4.10 Condensate System..................... 3-320 3.4.2.4.11 Steam Generator Chemical Addition......... 3-323 3.4.2.4.12 Circulating Water....................... 3-325 3.4.2.4.13 Generic RAI Issues...................... 3-328 3.4.3 Evaluation Findings..................................... 3-331 3.5 Containments, Structures, and Component Supports................ 3-332 3.5.1 Summary of Technical Information in the Application........... 3-332 3.5.2 Staff Evaluation....................................... 3-333 3.5.2.1 Aging Management Evaluations in the GALL Report That Are Relied On for License Renewal, Which Do Not Require Further Evaluation................... 3-337 3.5.2.2 Aging Management Evaluations in the GALL Report that Are Relied on for License Renewal, For Which GALL Recommends Further Evaluation.............. 3-338 3.5.2.2.1 Containments
....................... 3-338 3.5.2.2.2 Class I Structures.................... 3-350 3.5.2.2.3 Component Supports.................. 3-353 3.5.2.3 Aging Management Programs for Containment, Structures, and Component Supports........... 3-354 3.5.2.3.1 ASME Section XI, Subsection IWE Program 3-355 3.5.2.3.2 ASME Section XI, Subsection IWL Program 3-359 3.5.2.3.3 ASME Section XI, Subsection IWF Program 3-365 3.5.2.3.4 10 CFR Part 50, Appendix J Program..... 3-367 3.5.2.3.5 Structures Monitoring Program.......... 3-369 3.5.2.3.6 Dam Inspection Program............... 3-372 3.5.2.4 Aging Management Review of Plant-Specific Structures and Structural Components........................ 3-374 3.5.2.4.1 Containment........................ 3-375 3.5.2.4.2 Other Structures..................... 3-380 3.5.2.4.3 Component Supports.................. 3-386 3.5.3 Evaluation Findings.................................... 3-389 3.6 Electrical and Instrumentation and Controls........................ 3-391 3.6.1 Summary of Technical Information in the Application........... 3-391 3.6.2 Staff Evaluation....................................... 3-392 3.6.2.1 Aging Management Evaluations in the GALL Report That Are Relied On for License Renewal, Which Do Not Require Further Evaluation................... 3-394 3.6.2.2 Electrical Equipment Subject to Environmental Qualification
.............................. 3-394 3.6.2.3 Aging Management Programs for Electrical and Instrumentation and Controls Components....... 3-394 3.6.2.3.1 Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements....................... 3-395 3.6.2.3.2 Electrical Cables Used in Instrumentation Circuits Not Subject to 10 CFR 50.49 EQ Requirements That Are Sensitive to Reduction in Conductor Insulation Resistance.................. 3-400
xxii 3.6.2.3.3 Inaccessible Medium-Voltage Cable Not Subject to 10 CFR 50.49 EQ Requirements......... 3-405 3.6.2.4 Aging Management of Plant-Specific Components. 3-405 3.6.2.4.1 Bus Duct........................... 3-406 3.6.2.4.2 Non-EQ Electrical Penetration Assemblies. 3-408 3.6.2.4.3 High-Voltage Electrical Switchyard Bus.... 3-409 3.6.2.4.4 High-Voltage Transmission Conductors.... 3-410 3.6.2.4.5 High-Voltage Insulators................ 3-411 3.6.3 Evaluation Findings.................................... 3-411 4 TIME-LIMITED AGING ANALYSES......................................... 4-1 4.1 Identification of Time-Limited Aging Analyses
.......................... 4-1 4.1.1 Summary of Technical Information in the Application.............. 4-1 4.1.2 Staff Evaluation.......................................... 4-2 4.1.3 Conclusions............................................. 4-2 4.2 Reactor Vessel Neutron Embrittlement............................. 4-2 4.2.1 Summary of Technical Information in the Application............. 4-2 4.2.1.1 Pressurized Thermal Shock
.................... 4-2 4.2.1.2 Reactor Vessel Upper-Shelf Energy.............. 4-3 4.2.1.3 Plant Heatup/Cooldown (Pressure/Temperature) Curves
/Low-Temperature Overpressure Protection Power-Operated Relief Valve Setpoints................. 4-3 4.2.2 Staff Evaluation......................................... 4-4 4.2.2.1 Pressurized Thermal Shock
.................... 4-4 4.2.2.2 Reactor Vessel Upper-Shelf Energy.............. 4-6 4.2.2.3 Plant Heatup and Cooldown (Pressure/Temperature)
Curves/Low-Temperature Overpressure Protection Power-Operated Relief Valves Setpoints................ 4-8 4.2.3 UFSAR Supplement...................................... 4-9 4.2.4 Conclusions........................................... 4-10 4.3 Metal Fatigue.................................................. 4-10 4.3.1 Summary of Technical Information in the Application............. 4-11 4.3.2 Staff Evaluation......................................... 4-13 4.3.2.1 Explicit Fatigue Analysis (ASME Section III, Class A)..... 4-13 4.3.2.1.1 Pressurizer Surge Line Thermal Stratification.... 4-15 4.3.2.1.2 Pressurizer Insurge/Outsurge................ 4-16 4.3.2.1.3 Reactor Internals Hold Down Spring and Alignment Pins.................. 4-17 4.3.2.1.4 Auxiliary Feedwater Line Fatigue Analysis...... 4-17 4.3.2.2 Implicit Fatigue Design (ASME Section III, Class C, ANSI B31.1)
............................................... 4-19 4.3.2.3 Environmentally Assisted Fatigue Evaluation
........... 4-19 4.3.3 Conclusions............................................ 4-21 4.3.4 Reactor Vessel Underclad Cracking......................... 4-21 4.3.4.1 Summary of Technical Information in the Application
............................................... 4-21 4.3.4.2 Staff Evaluation............................. 4-21 4.3.4.3 Updated Final Safety Analysis Report Supplement....... 4-22 4.3.4.4 Conclusions................................ 4-22
xxiii 4.3.5 Containment Penetration Bellows Fatigue..................... 4-23 4.3.5.1 Summary of Technical Information in the Application..... 4-23 4.3.5.2 Staff Evaluation.................................. 4-23 4.3.5.3 Conclusions..................................... 4-24 4.3.6 Crane Cycle Load Limits.................................. 4-24 4.3.6.1 Summary of Technical Information in The Application..... 4-24 4.3.6.2 Staff Evaluation.................................. 4-25 4.3.6.3 Conclusions..................................... 4-26 4.4 Environmental Qualification of Electrical Equipment..................... 4-27 4.4.1 Electrical and I&C Component Environmental Qualification Analyses
..................................................... 4-27 4.4.1.1 Summary of Technical Information in the Application...... 4-27 4.4.1.2 Staff Evaluation............................. 4-29 4.4.1.3 Limitorque SBM Motor-Operated Valve ActuatorsOutside Containment............... 4-33 4.4.1.3 Conclusions................................ 4-35 4.4.2 GSI-168, Environmental Qualification of Electrical Components
... 4-35 4.4.2.1 Summary of Technical Information in the Application
......................................... 4-35 4.4.2.2 Staff Evaluation............................. 4-35 4.4.2.3 Conclusions................................ 4-35 4.5 Concrete Containment Tendon Loss of Prestress....................... 4-35 4.5.1 Summary of Technical Information in the Application............. 4-35 4.5.2 Staff Evaluation......................................... 4-36 4.5.3 Conclusions............................................ 4-39 4.6 Other TLAAs................................................... 4-39 4.6.1 Thermal Aging Embrittlement.............................. 4-39 4.6.1.1 Summary of Technical Information in the Application
............................................... 4-39 4.6.1.2 Staff Evaluation............................. 4-41 4.6.1.3 Updated Final Safety Analysis Report Supplement.. 4-43 4.6.1.4 Conclusions................................ 4-45 4.6.2 Foundation Pile Corrosion................................. 4-45 4.6.2.1 Summary of Technical Information in the Application..... 4-45 4.6.2.2 Staff Evaluation.................................. 4-45 4.6.2.3 Conclusions..................................... 4-46 4.6.3 Elimination of Containment Penetration Coolers................ 4-46 4.6.3.1 Summary of Technical Information in the Application..... 4-46 4.6.3.2 Staff Evaluation.................................. 4-47 4.6.3.3 Conclusions..................................... 4-47 4.6.4 Aging of Boraflex....................................... 4-47 4.6.4.1 Summary of Technical Information in the Application...... 4-47 4.6.4.2 Staff Evaluation.................................. 4-48 4.6.4.3 Updated Final Safety Analysis Report Supplement.. 4-49 4.6.4.4 Conclusions..................................... 4-49 5 REVIEW BY THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
......... 5-1 6 CONCLUSIONS........................................................ 6-1
xxiv Appendix A: COMMITMENT LISTINGS....................................... A-1 Appendix B: CHRONOLOGY............................................... B-1 Appendix C: PRINCIPAL CONTRIBUTORS................................... C-1 Appendix D: REFERENCES
............................................... D-1